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ML20138D335
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Category
TEXT-SAFETY REPORT  and REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
Accession number
ML20138D335  +
Atomic Element
Boron +, Iodine +, Krypton +, Hydrogen +, Xenon +  and Lead +
CFR
10 CFR 100 +, 10 CFR 50.59 +, 10 CFR 5019 +  and 10 CFR 50.53 +
Cornerstone
Initiating Events +
Correspondence
LD-82-001, Forwards Proprietary & Nonproprietary Versions of Cesec Digital Sumulation of C-E Nsss. Proprietary Version Available in Central Files Only +  and LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS +
Cross cutting aspect
S.0(f) +
Docket
05000285  +, 00285  +, 00382  +  and 00100  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Omaha Public Power District +
Generic letter
NRC Generic Letter 86-06, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML20138D335 +, ML20138D335 +, ML20138D335 +, ML20138D335 +, ML20138D335 +, ML20138D335 +, ML20138D335 +, ML20138D335 +, ML20138D335 +  and ML20138D335 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
In package
ML19303F306 +
Issue date
January 31, 1993  +
LD
LD-82-001, Forwards Proprietary & Nonproprietary Versions of Cesec Digital Sumulation of C-E Nsss. Proprietary Version Available in Central Files Only +  and LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS +
Manufacturer
Westinghouse +
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00:51:15, 12 December 2024  +
Page count
145  +
Power source
4V +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20138D335 +
Project stage
Request  +
SSC
3N-400 +  and 600I-u +
Scram
Manual Scram +  and Automatic Scram +
Site
Fort Calhoun +
Start date
January 31, 1993  +
State
Connecticut +  and Louisiana +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Steam Safety Valve +, Main Steam Line +, Control Rod +  and Main Steam +
Title
Nonproprietary OPPD Nuclear Analysis Reload Core Analysis, Methodology Transient & Accident Methods & Verification  +
Topic
Boric Acid +, Shutdown Margin +, Anticipated operational occurrence +, Loss of Offsite Power +, Fuel cladding +, Power change +, Coast down +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML2013/ML20138D335.pdf  +
 
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